ML041190540

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Limited Weld Examinations During End-of-Cycle 12, Refueling Outage
ML041190540
Person / Time
Site: Catawba Duke Energy icon.png
Issue date: 04/19/2004
From: Jamil D
Duke Energy Corp
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
04-CN-002
Download: ML041190540 (40)
v • d • e


Text

{{#Wiki_filter:, Duke D.M. JAMIL r Powere Vice President A Duke Energy Company Duke Power Catawba Nuclear Station 4800 Concord Rd. / CN01 VP York, SC 29745-9635 803 831 4251 803 831 3221 fax April 19, 2004 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555

Subject:

Duke Energy Corporation Catawba Nuclear Station, Unit 2 Docket Number 50-414 Request for Relief Number 04-CN-002 Limited Weld Examinations During End-of-Cycle 12 Refueling Outage Pursuant to 10 CFR 50.55a(g)(5)(iii), please find attached Request for Relief 04-CN-002. This request for relief is associated with limited weld examination coverage during the subject outage. The attachment to this letter contains all technical information necessary in support of this request for relief. Duke Energy Corporation is requesting NRC review and approval of this request at your earliest opportunity. There are no regulatory commitments contained in this letter or its attachment. If you have any questions concerning this material, please call L.J. Rudy at (803) 831-3084. Very truly yours, Dhiaa M. Jamil LJR/s Attachment oL2 www. duke-energy. corn

v N Document Control besk Page 2 April 19, 2004 xc (with attachment): L.A. Reyes, Regional Administrator U.S. Nuclear Regulatory Commission, Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30303 E.F. Guthrie, Senior Resident Inspector U.S. Nuclear Regulatory Commission Catawba Nuclear Station S.E. Peters, Project Manager (addressee only) U.S. Nuclear Regulatory Commission Mail Stop 0-8 G9 Washington, D.C. 20555-0001

Relief Request 04-CN-002 Page I of 6 Proposed Relief in Accordance with 10 CFR 50.55a(g)(5)(iii) Inservice Inspection Impracticality Duke Energy Corporation Catawba Nuclear Station - Unit 2 (EOC-12) Second 10-Year Interval - Inservice Inspection Plan Second Interval Start Date - August 19, 1996 Second Interval End Date - August 19, 2006 ASME Section XI Code - 1989 Edition with No Addenda

1.

II. & Ill. IV. V. VI. VIl. Limited System/ Code Requirement from Which Relief Is Basis for Relief Alternate Justification for Implementation Schedule Arealfeld I.D. Component for Requested: 100% Exam Volume Coverage Examinations Granting Relief Number Which Relief Is Exam Category or Testing Requested: Item No. Area or Weld to be Fig. No. Examined Limitation Percentage 2ASWINJF-SH-Seal Water Injection Category C-A, Item Number COi.020.012, See Paragraph "A" See Paragraph See Paragraph "H" See Paragraph "J" HD Filter 2A Shell-to ASME Section XI, Appendix m. m-4420 "F"" Head Figure Number IWC-2500-1 (a) Circumferential Volume Limitation: 50.94% Weld 2NI72-2 NI System Category C-F-I, Item Number C05.011.108, See Paragraph "B" See Paragraph See Paragraph "G" See Paragraph "J" Elbow-to-Tee Figure Number IWC-2500-7 (a) "F' Circumferential Scanning limitation: 75% Weld__ 2N172-3 NI System Category C-F-I, Item Number C05.011.109, See Paragraph "C" See Paragraph See Paragraph "G" See Paragraph "J" Tee-to-Reducer Figure Number IWC-2500-7 (a) "F. Circumferential Scanning limitation: 75% Weld 2NI88-3 NI System Category C-F-I, Item Number C05.011.142, See Paragraph "D" See Paragraph See Paragraph "G" See Paragraph 'J" Tee-to-Pipe Figure Number IWC-2500-7 (a) "FF Circumferential Scanning limitation: 75% Weld 2CFIOO-60 CF System Category C-F-I, Item Number C05.011.211, See Paragraph "E' See Paragraph See Paragraph I" See Paragraph "J" Valve 2CF168-to - Figure Number iWC-2500-7 (a) "F.. Elbow Scanning limitation: 75% Circumferential Weld

,v Request for Relief 04-CN-002 Page 2 of 6 IV. Basis for Relief Paragraph A: During the ultrasonic examination of the Seal Water Injection Filter 2A Shell-to-Head Circumferential Weld, 100% coverage of the required examination volume could not be obtained (See Attachment A-I). ASME, Section XI, Appendix III, III4420 requires scanning of the examination volume from two beam path directions. This requirement could not be complied with because of a sharp transition in thickness from the head to the shell. The examination coverage was limited to 50.94 %. The percentage of coverage reported represents the aggregate coverage of all scans performed on the weld. 62% (head side) of the required volume was examined in one axial direction, 27% (shell side) was examined in the other axial direction and 57% of the required volume was examined in two circumferential directions. In addition, austenitic weld metal characteristics prevent using the second sound path leg to obtain coverage. In order to achieve more coverage, the weld would have to be re-designed to allow scanning from both sides of the weld, which is impractical. The percentage of coverage reported represents the aggregate coverage of all scans performed on the weld. (Examination Data for Weld ID. Number 2ASWINJF-SH-HD is shown in Attachment A) (High Pressure Filter Assembly - Attachment A-I) Paragraph B: During the ultrasonic examination of the NI System Elbow-to Tee Circumferential Weld 2N172-2, coverage of the required examination volume could not be achieved from two axial and two circumferential directions. Duke Energy Corporation does not take credit for examining the far side on austenitic piping welds where the sound beam must penetrate the weld metal and access is restricted to one side of the weld. The examination coverage was limited to 75%. Because of the outside diameter taper on the tee side of the weld scanning in the axial direction from that side was not performed. In addition, austenitic weld metal characteristics prevent using the second sound path leg to obtain coverage. The percentage of coverage reported represents the aggregate coverage of all scans performed on the weld. 100% of the examination volume was covered in one axial direction and two circumferential directions. (Examination Data for Weld ID. Number ID. 2N172-2 is shown in Attachment B) Paragraph C: During the ultrasonic examination of the NI System Tee-to-Reducer Circumferential Weld 2N172-3, coverage of the required examination volume could not be achieved from two axial and two circumferential directions. Duke Energy Corporation does not take credit for examining the far side on austenitic piping welds where the sound beam must penetrate the weld metal and access is restricted to one side of the weld. The examination coverage was limited to 75%. Because of the outside diameter taper on the tee side of the weld scanning in the axial direction from that side was not performed. In addition, austenitic weld metal characteristics prevent using the second sound path leg to obtain coverage. The percentage of coverage reported represents the aggregate coverage of all scans performed on the weld. 100% of the examination volume was covered in one axial direction and two circumferential directions. In order to achieve more coverage, the weld would have to be re-designed to allow scanning from both sides of the weld, which is impractical. (Examination Data for Weld ID. Number ID. 2N172-3 is shown in Attachment C) Paragraph D: During the ultrasonic examination of the NI System Tee-to-Pipe Circumferential Weld 2N188-3, coverage of the required examination volume could not be achieved from two axial and two circumferential directions. Duke

Request for Relief 04-CN-002 Page 3 of 6 Energy Corporation does not take credit for examining the far side on austenitic piping welds where the sound beam must penetrate the weld metal and access is restricted to one side of the weld. The examination coverage was limited to 75%. Because of the outside diameter taper on the tee side of the weld scanning in the axial direction from that side was not performed. In addition, austenitic weld metal characteristics prevent using the second sound path leg to obtain coverage. The percentage of coverage reported represents the aggregate coverage of all scans performed on the weld. 100% of the examination volume was covered in one axial direction and two circumferential directions. In order to achieve more coverage, the weld would have to be re-designed to allow scanning from both sides of the weld, which is impractical. (Examination Data for Weld ID. Number ID. 2N188-3 is shown in Attachment D) Paragraph E: During the ultrasonic examination of the CF System Valve 2CF168-to-Elbow'Circumferential Weld 2CF100-60, coverage of the required examination volume could not be achieved from two axial and two circumferential directions. Duke Energy Corporation does not take credit for examining the far side on austenitic piping welds where the sound beam must penetrate the weld metal and access is restricted to one side of the weld. The examination coverage was limited to 75%. Because of the outside diameter taper on the valve side of the weld, scanning in the axial direction from that side was not performed. In addition, austenitic weld metal characteristics prevent using the second sound path leg to obtain coverage. The percentage of coverage reported represents the aggregate coverage of all scans performed on the weld. 100% of the examination volume was covered in one axial direction and two circumferential directions. In order to achieve more coverage, the weld would have to be re-designed to allow scanning from both sides of the weld, which is impractical. (Examination Data for Weld ID. Number ID. 2CF100-60 is shown in Attachment E) V. Alternate Examinations or Testing Paragraph F: There are no scheduled alternative examinations or testing. However; Duke Energy proposes to use required future pressure test and VT-2 visual examinations to complement the limited ultrasonic examination coverage. Based on the coverage and results of the required volumetric and surface examinations this outage and the Code required pressure testing (VT-2) examinations, it is Duke's belief that this combination of examinations provides a reasonable assurance of component integrity. VI. Justification for Granting Relief Paragraph G: Ultrasonic examinations were performed using personnel, procedures and equipment qualified in accordance with ASME Section XI, Appendix VIII, 1995 Edition through the 1996 Addenda as administered through the Performance Demonstration Initiative (PDI). Currently PDI does not issue a qualification for single sided examination of austenitic piping welds. However a best effort examination was performed on the weld metal and far side base material using refracted longitudinal waves, which is considered to be the best available technique. The NI system welds that were identified in the relief request (2N192-4, 2N172-3, 2N188-3) are on piping from the ND system to the Hot and Cold Leg injection lines. These pipes are not in an active portion of the system. The pipes are filled with FW (Refueling Water System) system water at a low pressure FWST (Refueling Water Storage Tank) static head. Since this piping is in the Containment Building, if a small leak in the weld were to occur, it is highly likely that the leak would continue for a significant amount of time before being noticed.

Request for Relief 04-CN-002 Page 4 of 6 Since this is low energy FW 3wvater, a leak would be undetectable usinig ihe Containment Atmosphere Gaseous and Particulate Radioactivity Monitoring (EMF monitors 38 and 39). The Containment Ventilation Unit Condensate Drain Tank level would likely not increase since the water leaking through the pipe is low energy and the location of the weld in not in a hot environment. A leak would need to be significant before a decreasing trend is noticed on the FWST level. It is likely that a leak in the identified NI system welds would only be discovered during a refueling outage, beginning with the pre-outage containment walkdown. The water in the pipe is highly borated and would likely leave a significant amount of boron accumulation on the pipe and surrounding area. This boron accumulation would most likely be noticed during the course of a refueling outage. There is also a possibility that a leak would be discovered by monitoring the Containment Floor and Equipment Sump level/inputs. However, since there is always an input to Containment Floor and Equipment Sump A, the leak would not be noticed unless it was significant. Significant leakage through the welds would likely be identified by Containment Floor and Equipment Sump level indication. There would have to be a gross failure of the welds for any significant impact to occur in the Refueling Water Storage Tank (FWST) level. One of these welds, Elbow-to-Pipe Weld #2NI924, received an ultrasonic and a dye penetrant examination during the First Inspection Interval. There were no reportable conditions found. In summary, it is possible for a small leak to develop in welds 2N172-2, 2NI72-3, and 2NI88-3 and remain unnoticed for several months. This is mainly due to the pipe being filled with low energy FW system water. The systems and processes established to detect leaks inside containment mainly focus on pipes containing high energy water or water with high amounts of radiological activity. However, with 75% scanning coverage for Weld ID's 2NI72-2, 2NI72-3 and 2NI88-3 obtained, and with the fact no indications were found during the surface examinations on these welds, reasonable assurance of weld integrity is provided. Paragraph H: Ultrasonic examinations were performed in accordance with ASME Section XI, Appendix III. The examination performed on the weld metal and far side base material used refracted longitudinal waves, which is considered to be the best available technique. Seal Water Injection Filter 2A Shell-to-Head Circumferential Weld 2ASWINJF-SH-HD is located outside containment. If a leak were to develop at this weld location, the instrumentation available to the operators for detection and monitoring of leakage would provide prompt and qualitative information necessary to permit them to take immediate corrective action. If a leak should develop in this aforementioned location, the corrective action would be to isolate the leak and place the other seal water injection filter in service. This corrective action is governed by approved procedures. Additionally, other indicators are also available to the operator that a leak exists: Charging / Letdown system mismatches. Inspection for leakage around the "filter casing head" whenever the filters are changed. Procedure OP/l/A/6200/001, Chemical and Volume Control System, has a step to "verify no leakage from around the filter casing head". U

Request for Relief 04-CN-002 Page 5 of 6 Paragraph I: Ultrasonic examinations were performed using personnel, procedures and equipment qualified in accordance with ASME Section XI, Appendix VIII, 1995 Edition through the 1996 Addenda as administered through the Performance Demonstration Initiative (PDI). Currently PDI does not issue a qualification for single sided examination of austenitic piping welds. However, a best effort examination was performed on the weld metal and far side base material using refracted longitudinal waves, which is considered to be the best available technique. The CF system weld identified in the relief request is on Unit 2 feedwater piping that maintains a constant tempering flow to the auxiliary feedwater nozzle on the "C" Steam Generator. Fluid within the piping is at steam generator feedwater temperature and pressure conditions during normal operations. The piping is rated Class B. The piping is routed through a floor penetration on the 594' elevation of the Unit 2 Interior Doghouse. The subject weld is located several feet from the handrail for the observation platform for this elevation. The weld area is at eye level and a direct line of sight to the weld area is maintained along normal travel paths on this platform. The operations staff conducts weekly inspections of the Interior Doghouse with specific instructions to identify steam or secondary side water leaks. If a leak were to develop at the weld location discussed in the relief request, some of the high temperature fluid would immediately flash to steam. Blanket insulation is installed on the piping downstream of the weld area. However, there is a gap in the insulation coverage in the area of the weld at the transition from valve 2CF168 to the downstream piping. This insulation configuration ensures that weld leakage would be readily apparent to personnel traveling through the area. In addition to the periodic room inspections, safety-grade level switches are installed on the foundation floors of the Doghouse rooms. These switches are designed to protect safety-related components in the room from a pipe leak and subsequent room flooding. A safety-related feedwater isolation signal for the "B" and "C" Steam Generators would be generated if leakage from the weld accumulated on the floor below the weld area. If a leak were discovered, a work request would be written and the leak would be evaluated under the Fluid Leak Management process. Since the piping is rated Class B, the criteria of Selected Licensee Commitments (SLC) 16.5-5 "Structural Integrity" would be applicable. Weld repairs would require a unit downpower as the weld area can not be isolated from the main feedwater piping.

Request for Relief 04-CN-002 Page 6 of 6 VII. Implementation Schedule Paragraph J: The scheduled second 10-year interval plan code examination was performed on the referenced welds resulting in limited volumetric coverage. No additional examinations are planned for the welds during the current inspection interval. The same welds may be examined again as part of the next (third) 10-year interval plan, depending on the applicable code year edition and addenda requirements adopted in the future. VIII. Other Information The following individuals contributed to the development of this RFR: Jim McArdle (NDE Level III Inspector) provided UT related information for Sections II through VI Ari Tuckman and Charles Mohr (CNS Systems Engineers) provided a portion of Section VI Andy Hogge (Sponsor) compiled the remaining sections. Sponsored By: Approved By: Xr)1z-( (- 1z,8 4/16104 A Date Ae ,A A Date 4/7/ 4

DUKE POWER COMPANY Exam Start: 1320 NDE-UT-3A ULTRASONIC EXAMINATION DATA SHEET FOR LAMINAR REFLECTORS Exam Finish: 1325 Revision 2 Station: CNS Unit: 2 ComponentMWeld ID: 2ASWINJF-SH-HD Date: 10130/2001 Nominal Material Thickness (in): 0.674 Weld Length (in.): 14.1 Surface Temperature: 87° Deg F Measured Material Thickness (in): .398 Lo: 9.2.2 Pyrometer S/N: MCNDE 27008 Surface Condition. AS GROUND Calibration Sheet No: Cal Due: 2114/2002 Examiner: DavidIZimmerman vel: Il 0102062 Configuration: Shell to Head Examiner. Winfred C. Leeper/ i II S2 Flow SI Procedure: NDE-640 1e: 1 FC: SHELL to HEAD Ampl LI WI Mp1 W2 Mp2 L2 WI Mp1 W2 Mp2 IND rem 2rem a rem z rem 2rem Z rem 2rem rem 2 rem a rem 2rem Exam D NO. 4 BW BW BW BW BW BW BW BW BW BW BW Surf. amps LOB LOB LOB LOB LOB LOB LOB LOB LOB LOB LOB NRI 0' Remarks: *FC 95-18, 95-19 Limitations: see NDE-UT-4 0 None: 0 Sheet l of Reviewed By: Level: Date: Aftq ized Inspector, Date: Item No: G7 /04d)if4 I j "V\\6Lr 10-3S^Ci C01.020.012 I U I 116) 4) r,e AZ/A

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DUKE POWER COMPANY Exam Start: 1337 Form NDE-UT-2A ULTRASONIC EXAMINATION DATA SHEET FOR PLANAR REFLECTORS Exam Finish: 1401 Revision 4 Station: CNS Unit: 2 ComponentNVeld ID: 2ASWINJF-SH-HD Date: 10/30/2001 Weld Length (in.): 14.1 Surface Condition: AS GROUND Lo: 9.2.2 Surface Temperature: 87 0 F Examiner: David ZimmermanA.Y. Cevel: IlIl Scans: Pyrometer S/N: MCNDE 27008 v Cal Due: 2/14/2002 Examiner: Winfred C. Leeper 11 45 [ 47 dB 70 z dB Podr ND60k 4Configuration: Shell to Head Procedure: NDE-630 Rev: 2 FC: 45T i 55.5 dB 70T 0 _dB HEAD Flow SHELL 99-02 60 0 dB Si to S2 Calibration Sheet No: 60T d B Scan Surface: OD d0 Applies to NDE-680 only 0102063, 0102064, 0102065 Other: 45L (a) 62.5 dB SkewAngle: N/A Max Mp W L Beam Exam IND # Max Max Max LI L2 W1 Mp1 W2 Mp2 Dir. Surf. Scan Damps 20%dac 20%dac 20%dac 20%dac 20%dac 20%dac DO NOT W ITE HMA HMA HMA HMA HMA HMA 0 NOT WRIT IN T.IS SPCE 50%dac 50%dac 50%dac 50%dac 50%dac 50%dac IN THIS SPACE 100%dac 100%dac 100%dac 100%dac 100%dac 100%dac NRI 450 Remarks: Limitations: (see NDE-UT-4) Z 90% or greater coverage obtained: yes no Sheet 3 of 8 Reviewed Bv: Level: Date: thorized Inspector: Date: Item No: /0I/31/, C01.020.012 4.

DUKE POWER COMPANY FORM NDE-UT-4 1ST LIMITATION REPORT Rcvision 1 Component/Weld ID: 2ASWINJF-SH-HD Item No: C01.020.012 Remarks: SURFACE BEAM DIRECTION DUE TO SHELL TO HEAD 0 NO SCAN CONFIGURATION. 0 LIMITED SCAN Ed 1 0 2 0 1 2 cwO ccw FROM L N/A to L N/A INCHES FROM WO .3" to BEYOND ANGLE: 0 0 E0 45 0 60 0 Other FROM 0 DEG to 360 DEG SURFACE BEAM DIRECTION O NO SCAN O LIMITEDSCAN 0 1 0 2 O 1 O 2 O cw O ccw FROM L to L INCHES FROM WO to ANGLE: 0 0 0 45 0 60 0 Other FROM DEG to DEG SURFACE BEAM DIRECTION 0 NO SCAN OLIMITED SCAN 0 10 2 0 1 O 2 O cw O ccw FROM L to L INCHES FROM WO to _ ANGLE: 0 0 0 45 0 60 0 Other FROM DEG to DEG SURFACE BEAM DIRECTION 0 NO SCAN 0 LIMITED SCAN 01 0 2 0 1 0 2 0 cw O ccw FROM L to L INCHES FROM WO to ANGLE: 0 0 0 45 0 60 0 Other FROM DEG to Prepared By: 2 Level:. Date: Sketch(s) attached N yes 0 no Sheet -3of Reviewed By: Date: Authorized Inspector: L4 Date: )31310)

DUKE POWER COMPANY NDE-91-1 Limited Examination Coverage Worksheet Revision 0 Examination Volume/Area Defined L Base Metal z Weld D Near Surface ° Boltinq E Inner Radius Area Calculation Volume Calculation SEE DRWGS. FOR CALCULATIONS 0.77 SQ.IN. X 14.1 IN. = 10.86 CU.IN. 0.77 SQ.IN. Coverage Calculations Area Length Volume Volume Beam Examined Examined Examined Required Percent Coverage Scan # Angle Direction (sq.in.) (in.) (cu.in.) (cu.in.) 1 45 S2 0.21 14.1 2.96 10.86 2 45 S1 0.48 14.1 6.77 10.86 3 45 CW 0.44 14.1 6.2 10.86 4 45 cw 0.44 14.1 6.2 10.86 22.13 43.44 50.94 Item No: C_1.020.012 Prepared By: David Zimmerman Level: III Date: 10/30/2001 Reviewed By: Adz H o Level: -M Date:o,30.A, ff f C-

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L2 ?. rem .BW ..LOB WI a rem BW LOB Mpl a rem BW LOB W2 a rem BW LOB Mp2 ?. rem B1W. LOB' Exam Surf.- --- Damps

4.

+ + +

4.

4 4 4 4 4 4 4 + NRI 0. Remarks: FC 95-19, 02-29, 03-02, 03-04, 03-08 Limitations: see NDE-LIT-4 E None: Sheet 2 -of Reviewed By:jf .LematL Date: A p~d Inspe to: Date: Item No: LI ~LLI~5 /~'3C05.011.108 V N

DUKE POWER COMPANY NDE-UT-UT PROFILE/PLOT SHEET Revision.1 I EXAMINATION SURFACE 1 - TM; Whoa' - EXAMINATION SURFACE 2 WELD 4 111111 II 3 2 1 I liii ii Ii I I IIL P0( )I 0~ AtN ee 4#>6p r\\ < ; < 'O 0.o O 90 111 1111 1111 M I L 1111L Ill 3 4 I I I 1 ((II. I I I 4. .5 4-1 .5 2 e 2.5 I 3 3 II.I Component ID/Weld No. u -7 dor -77Z--7 . Remarks: Item No: (L S.oll. 10l m Level: Il Da te: I Profile taken 270 at: A- \\I e L 0 1 80 Set :~ofW 5 03 Revlewed BY: .1 le-l> a-. A ILevel: L-. Date: 3 It-6,A5 I = 7 U i IV J .I IAuthordzed Inspector. M-d Wao u v-

DUKE POWER COMPANY NDE-UT-S UT PROFILE/PLOT SHEET Revislon.1 EXAMINATION SURFACE 1 - TE ,8oL-EXAMINATION SURFACE 2 4. III 3 2 WELD I 1 1 Jill liii liii liii I 1111 111111 iR[I I 11111111 2 dilI 3 I11 III lii 4 liii liii JIJI1 D X A \\ / + I i ~~ / - 1 ' 1.5 2 2.5 1 3 Component ID/Weld No. U 2.. . Remarks: - I o 6,0/,, CoV&5:A(,C. P95e i4'E:-q 1

/-~ I Item No
C, j.

I. Io Examiner I Level: l IDatc: 3l13l? Profile taken 270 lat:. - 18 I L 9 , f5-- - 3 AReviewed By: A_ level:.2L l Date: 3./~of ,fiD Ote: 3-8^> X I. lAuthorlzed Inspector. -- ov u

DUKE POWER COMPANY FORM NDE-UT-4 ISI LIMITATION REPORT Revision 1 Component/Weld ID: 2NI72-2 Item No: C05.011.108 Remarks: SURFACE BEAM DIRECTION Valve Configuration - 100% scan E2E NO SCAN coverage obtained per NDE-91. O LIMITED SCAN 01 02 0 1O20cwOccw FROM L toL - -L - INCHES FROM WO-- C/L to Beyond ANGLE: O 0 0 45 El 60 0l Other FROM 0 _ DEG to 360 DEG SURFACE BEAM DIRECTION 0 NO SCAN OLIMITED SCAN 0 1 0 2 0 1 0 2 Elcw O ccw FROM L to L INCHES FROM WO to ANGLE: O 0 0 45 0 60 0 Other FROM DEG to __ DEG-SURFACE BEAM DIRECTION 0 NO SCAN 0 LIMITEDSCAN 0 1 0 2 0 1 0 2 0 cw E ccw FROM L to L INCHES FROM WO to ANGLE: O 0 0 45 0 60 0 Other FROM DEG to DEG SURFACE BEAM DIRECTION 0 NO SCAN E LIMITED SCAN 01 02 l 1 a 2 E cw O ccw FROM L to L INCHES FROM WO to ANGLE: 0 0 45 0 600 tler FROM DEG to Prepared By. Jay Eaton Level: III Date: 3/13/2003 Sketch(s) attac ed 0 yes 0 no Sheet jjof Reviewed By:-Z, Date: 3. I Cf l Authorized Inspector: Date:318 C3 J+1 V V .1

Catawba Unit 2 BOC 12 No Recordable Indications Calibration Sheet # 6 3 0 Ca-S< Component I.D. 42 A1 72 -3 Item # Cos.oCi. /oc et (ua3 4s1,6F ad Xo

,o A

r c7

DUKE POWER COMPANY FORM NDE-UT-4 ISI LIMITATION REPORT Revision 1 Component/Weld ID: 2NI72-3 Item No: C05.011.109 Remarks: SURFACE BEAM DIRECTION Valve Configuration - 100% scan El NO SCAN 1 coverage obtained per NDE-91. o LIMITEDSCAN ,Zi1 E2 LXJ1)6J20cw ccw FROM L -- to L INCHES FROM WO _ C/L to Beyond ANGLE: a o 0 45 El 60 0 Other FROM 0 DEG to 360 DEG SURFACE BEAM DIRECTION 0 NO SCAN O LIMITEDSCAN 1 02 l 1 E 2 E cw E ccw FROM L to L INCHES FROM WO to ANGLE: 0 0 0 45 0 60 a Other FROM DEG to DEG SURFACE BEAM DIRECTION O NO SCAN 0 LIMITEDSCAN 0 1 0 2 0 1 0 2 0 cw 0 ccw FROM L to L INCHES FROM WO to ANGLE: 0 0 0 45 0 60 0 Other FROM _ _ DEG to _ DEG SURFACE BEAM DIRECTION 0 NO SCAN 0 LIMITED SCAN 0 1 0 2 0 1 0 2 0 cw 0 ccw FROM L to L-INCHES FROM WO to ANGLE: D 0 0 45 0 60 0 t ter FROM DEGto __ Prepared By Jay Eaton Level: III Date: 3/13/2003 Sketch(s) attac d 0 yes no Sheet of 2 Reviewed By: Date: 3- / t1l Authorized Inspector: Date: 3..- o3 ,\\

DUKE POWER COMPANY NDE-UT-5 UT PROFILE/PLOT SHEET Revision.1 EXAMINATION SURFACE 1 - 14 £Qc- -r'CE-EXAMINATION SURFACE 2 4 I 11 I II' I 3 2 WELD I I*

    • ll Ill ll tI II 1

II 'III 1 2 I 11 3 III 4 lii III II 1I'1 (IIII I I I a I I I I I a I .5 X- -qz, N  -/ 1% 1,.- I 1 1.5 2 2.5 I 3 Component ID/Weld No. z 3 Remarks: A Item No: Czf Ol cO Examiner. Level: -\\ Datc: 31i3l[3 Reviewed By: LeveL Date, 3,, o 3 jAuthorized inspector Date:. J o3 u 270 -T-

DUKE POWER COMPANY Exam Start: 1151 NDE-UT-3A ULTRASONIC EXAMINATION DATA SHEET FOR LAMINAR REFLECTORS Exam Finish: 1155 Revision 2 Station: Catawba lUnit 2 Component/Weld ID: 2NI88-3 Date: 3/11/2003 Nominal Material Thickness (in): 0.906 Weld Length (in.): 27.3 Surface Temperature: 75° Deg F Measured Material Thickness (in): .893 Lo: 9.1.1.2 Pyrometer S/N: MCNDE 27227 Surface Condition: AS GROUND Calibration Sheet No: Cal Due: 5111/2003 Examiner Gary J. Moss, Level: II 0302040 Configuration: CIRC. Examiner James L. Panel I lvel: II S2 Flow S1 Procedure: NDE-64d Rev: 1 FC: PIPE to TEE Ampl LI WI MpI W2 Mp2 L2 Wi MpI W2 Mp2 2N rem 2 rem 2 rem 2 rem a rem 2 rem arem a rem 2 rem 2rem rem Exam Damps NO. 4 BW 8W BW BW BW BW BW SW BW SW BW Surf. p LOB LOB LOB LOB LOB LOB LOB LOB LOB LOB LOB NRI 0 Remarks: FC 95-19, 02-29, 03-02, 03-04, 03-08 Limitations: see NDE-UT-4 D None: l Sheet l of Reviewed By: Level: Date: A Date: Item No: A23*36 I,' S-3 C05.011.142 36 AMyY\\ I -70te vZ// /6/V-6'c*> cA°/ki5Vf p

DUKE POWER COMPANY NDE-UT-5 UT PROFILEIPLOT SHEET RevIsI6n.1

  • EXAMINATION SURFA(

4 3 CE 1 WELD EXAMINATION SURFACE 2 ~IIII IIIi liii 2 1 3? l ii lii _Do i% iia 11 III 3 liiiI 4 III 11111 liii i .5 S_ 4 7h,/-- I 1.52,___I_ 21 2.5 3 Component ID/Weld No. 2Nx988-3 U

Remarks:

270 90 Item No: a0s*. >/I. /,'a A\\... !Examiner: AlQ.I\\)a/h ILevel: %- I Date: 3-o1 y ,RevIewed By: 0,F_ AIIAQZ.4-1 L eve: Date: 3.f2.63 {1f Date: 3 -)8 (C2 ,?-of T ,l, A- + Autorived Irxsp-ectoK &Am,'i T N v

DUKE POWER COMPANY FORM NDE-UT-10 ULTRASONIC INDICATION RECORD FOR PIPING Revision 0 Station: Catawba Unit: 2 Component/Neld ID: 2NI88-3 Date: 3/11/2003 Surface Condition: AS GROUND Item No: C05.011.142 Examiner: Gary J. Moss evel: II Procedure: NDE-600 Rev: 14 FC: Examiner: James L. Panel yel: Lo: 9.1.1.2 Configuration: CIRC. Calibration Sheet No: 0302042, 0302043 PIPE to TEE Scan Surface: OD Mp W L LI L2 Beam Exam IND FSH Max Max Max 20 % FSH 20 % FSH Dir. Surf. Scan Damps Remarks 1 60° 80 1.6 1.1 360 INT. 1 2 AXIAL NO 2 60tL 85 1.6 1.1 360 INT. 1 2 AXIAL NO Reviewed Bv: Level: Date: A riz dInspe oy: Date: S 3 o J 3 1 23 /8 Sheet of7

DUKE POWER COMPANY NDE-UT-5 UT PROFILE/PLOT SHEET Revislon.1

  • EXAMINATION SURFACE 1 WI 4

3 2 1 1111 III 1111 III .1. n i LU IVl liii lii lii EXAMINATION SURFACE 2 2 3 4 lIII li l l I I III ii IIII: .5 i 110 I 1.11 I .5 4 e '41t qy',, ,,e 2 2.5 3 _f Component ID/Weld No. T A-3 u

Remarks:

270 Item No: cogo/. V-Examiner f,~ -Level: z l Date: 3/_I/e Reviewed By/ : Level:.. Date: 3*I2-c 3 of I AUthohzed Ins6Ttor. i'u Mel '. 1al/ Date: 3~ /R -a\\ Io l t r I V JI Ate: ,?s L- -N-

.I DUKE POWER COMPANY NDE-U-5 UT PROFILE/PLOT SHEET Revision.1 EXAMINATION SURFACE 1 4 MII I1 3 2 I II11111 1111iL L WELD W >

q.

i q-', I I I II llll1 EXAMINATION SURFACE 2 2 IL .I 11111111 3 I1 IlIII 4 I I 1 11111 I'll .5 i -L 1 £E I.<. 2.5 3 _~ 1) u Component ID/Weld No. It,- .3

Remarks: loo-. 3LuAA

-M R lPoff 9' Item No: cox o/I. Antd. IExamIner G t b Level: r Date: 3/,/c 270 3 Reviewed Bv:/ I Level::- Au h rzdI nspe to_ Da t e:-? -/ 2 _ 6 Datc:is IB 03

DUKE POWER COMPANY Form NDE-UT-8 ULTRASONIC INDICATION RESOLUTION SHEET Revision 1 Acceptance Standard: IND. #1 & #2 ARE GEOMETRIC REFLECTOR OFF ID COUNTERBORE. CONFIRMED PER USE OF 70° WEDGE ON 600 DUCER AND USE OF WSY-70. Item No: C05.011.142 Acceptable Indications: IND. #1 & #2 Rejectable Indications: NONE These indications have been compared with previous ultrasonic data E} Yes El No previous data available Examiner: / Level: Date: Sht o Gary J. Moss A Ace11 3/11/2003 Reviewr l Level: Date: Au e Ise= ae t)6 /, =- 12 -63 A i 3 -)8'63

DUKE POWER COMPANY FORM NDE-UT-4 ISI LIMITATION REPORT Revision 1 Component/Weld ID: 2NI88-3 Item No: C05.011.142 Remarks: SURFACE BEAM DIRECTION DUE TO TEE CONFIGURATION 100% El NO SCAN COVERAGE E LIMITEDSCAN E1 02 0 I 0 2 0 cw E ccw FROM L -- to L - INCHES FROM WO CL to BEYOND ANGLE: 0 0 0 45 El 60 0 Other FROM 0 DEG to 360 DEG SURFACE BEAM DIRECTION o NO SCAN El LIMITED SCAN 1 22 0 1 0 2 0 cw l ccw FROM L to L INCHES FROM WO to ANGLE: 0 0 0 45 0 60 0 Other -_a-_FROM. DEG to DEG. SURFACE - BEAM DIRECTION....... El NO SCAN O LIMITED SCAN El 02 01 0 2 El cw ccw FROM L to L INCHES FROM WO to ANGLE: E 0 El 45 0 60 0 Other FROM DEG to DEG El NO SCAN El LIMITED SCAN 0 FROM L -- to L_ _____ ANGLE: 0 0 0 45 0 60 0 Other URFACE BEAM DIRECTION 11 0 2El El2El cw ccw INCHES FROM WO -- to FROM DEG to J

FORM NDE-UT-4 DUKE POWER COMPANY ISI LIMITATION REPORT Revision 1 Component/Veld ID: 2CF100-60 Item No: C05.011.211 Remarks: SURFACE BEAM DIRECTION VALVE CONFIG. - FULL COVERAGE {] NO SCAN OBTAINED FROM OPPOSITE SIDE 0 LIMITED SCAN E 1 i9 2 [Z 1 El 2 0l cw El ccw FROM L N/A to L ___N/A INCHES FROM WO C/L__- to BEYOND ANGLE: El 0 a1 45 Li 60 0l Other FROM 0 _ DEG to 360 DEG SURFACE BEAM DIRECTION a NO SCAN 0LIMITED SCAN E El2 E 2Elcw cow FROM L to L INCHES FROM WO to ANGLE: 0 0 E 45 El 60 El Other FROM DEG to DEG SURFACE BEAM DIRECTION E NO SCAN O LIMITED SCAN E i 0 2El El2 0 cw El ccw FROM L to L INCHES FROM WO to ANGLE: El 0 El 45 El 60 El Other FROM DEG to DEG El NO SCAN El LIMITED SCAN FROM L - toL ANGLE: E 0 El45 0 60 0 Other SURFACE BEAM DIRECTION 0 1 0 2 El 1 El 2 El cw El ccw INCHES FROM WO to FROM DEG to Prepared By: David K. Reviewed By: I I 1416161L--725 7- = -7e _eA4eeZ 7- -Z--

  1.  4,

4-

.9 DUKE POWER COMPANY NDE-UT-5 UT PROFILE/PLOT SHEET Revision.1 EXAMINATION SURFACE 1 et. J 4 3 2 11 1 1 II l IIII II 1 1 I II II I I. ~1 1 I WELD s/ALtv -EXAMINATION SURFACE 2 I 1I III 1111 Il 2 I III 3 III I 1111 4 1 11 1 IIII 111.1 l_I_ I l .5 I - I I 1.5 2-2.5 3 r'mr-,n^nni-Ifln/WDri MN,- VIII) JI~III I f/ J Iu IIV. z.cY Iv op t E

Remarks:

(,Q0 C Tzia61A 5 s _A ) Item No: Z / I Examiner. lLcvel: l Dat: e 270 6 3 ,Reviewed By: kJV 7, u L~qvel: _L} Date: S

3. o Yi Da te: 3 ) P,,o3 A u e

-o e lAuthorized Inspector m, G-1l '-I

DUKE POWER COMPANY FORM NDE-UT-10 ULTRASONIC INDICATION RECORD FOR PIPING Revision 0 Station: Catawba I Unit: 2 Component/Weld ID: 2CF100-60 Date: 3/12/2003 Surface Condition: AS GROUND Item No: C05.011.211 Examiner: David Zimmerman Level: III Procedure: NDE-600 Rev: 14 FC: L l Examiner: Winfred C. Leepe rl kvel: II Lo: 9.1.1.2 Configuration: CIRC. WELD Calibration Sheet No: 0302049, 0302050 S2-VALVE to S1-ELBOW Scan Surface: OD °4 Mp W L Li L2 Beam Exam I IN $FSH Max Max Max 20 % FSH 20 % FSH Dir. Surf. Sa ap eak 1 60° 1.10 80 0.9 360 INT. IND. 2 1 AXIAL NO Reviewed Bv l Level: Date: orized In tor: Date: 3*/3-5 n CSheet of__

I

  • I DU EP W RC MA YExam Start:

1047 NDE-UT-3A ULTRASONIC EXAMINATION DATA SHEET FOR LAMINAR REFLECTORS Exam Finish: 1050 Revision 2 Station: Catawba FUnit: 2 ComponentNWeld ID: 2CF100-60 Date: 3(12/2003 Nominal Material Thickness (in): 0.432 Weld Length (in.): 20.8 Surface Temperature: 61 Deg F Measured Material Thickness (in): 0.419 Lo: 9.1.1.2 Pyrometer S/N: MCNDE 27227 Surface Condition: AS GROUND Calibration Sheet No: Cal Due: 5/11/2003 Emie:DvdZmemnLee:II 0302048 Configuration: CIRC. WELD Examiner: Winfred C. Leepe/ ,/evel: II S2 Flow S1 Procedure: NDE-640 v:i

  • VLE t

LO IND NO. .4 AmpI

- rem BW LOB Li z rem BW LOB Wi a rem BW LOB Mpl a rem 8W LOB W2 a rem 8W LOB Mp2

> rem BW LOB L2 ?- rem 8W LOB Wi ?. rem BW LOB IVpl ?- rem 8W LOB W2 ?- rem 8W LOB Mp2 ?- rem BW LOB Exam Surf. Damps 1* 1* 1* NRI 00 Remarks:

  • FC 95-19, 02-29, 03-02, 03-04, 03-08 Limitations:

see NDE-UT-4 0 None: ~ Sheet j f Reviewed By: /Level: Date: t 4rized Inspect Date: Item No:

DUKE POWER COMPANY NDE-UT-5 UT PROFILE/PLOT SHEET Revision.1 -tVA1UIMATICXM CllDCArC I 2; / IA, M LVA INIATIrnkl ClIDFCA fC I Lj^^llYI1t% I I'JIN *JUPNMAtLC I C E I. 4 3 I111 1 1. I 11111111 2 WELD _. M %-_,U LAMIVIII N I I'i QurXrM'.u. c-I I 2 3 Il L L L1iii I II ul~ 11111 1111111(1111 4 111 llI IIII .5 I I 1.I 2 2.5 3 Component ID/Weld No. U '7-o i.) t-o . Remarks: 270 Item No: } S A Exa miner JA.X2 ,Reviewed By: _E..yf _o _ _to I Level: 7 I Da tc: -S 1oz , _ J Level: -auj pa te: 3..1 3-6 I Zi/ Date: 3, 16 Cm v. lAuthorized inspecto6. c/i 1601i 'V

'I DUKE POWER COMPANY NDE-UT-5 UT PROFILE./PLOT SHEET RevisIon.1 EXAMINATION SURFACE 1 (eI.ot Z tLve -EXAMINATION SURFACE 2 WELD 4 1111 3 11111 1.111 2 1 1 111111 1- 'IQJ ILLLL liLLI I I lii 1 I I 1111III 2 1111 I 3 II1 4 I I 111111111[ 11.1 i Ii .5 l 1.5 2 2.5 3 Component ID/Weld No. u -C. I d (i -0 (e . Remarks: Item No: LN ve:CO OIL l a I Examiner. L1evel:~ - Date:_ z&?/o 270 -5 Rpvlpwpd Rv: i /S--,_ I ILevel:l.2 , 8,_....'( A I. a 1 t X l Date:3./3.63 Date: JI#o3 IAtoie Inspector. t',.- 1Autodzed Inspector. ktThu34

.DUKE POWER COMPANY Form NDE-UT-8 ULTRASONIC INDICATION RESOLUTION SHEET Revision 1 Acceptance Standard: IND. 1 - Geometrical indication from weld root configuration. 70° shear produced less than 50% amplitude. Signal would not hold up to skew. Plotting and review of radiographs support this detemination. Item No: C05.011.211 Acceptable Indications: 1 Rejectable Indications: None. These indications have been compared with previous ultrasonic data El Yes E No previous data available Examiner: Level: Date: f David Zimmerman L_ III 3/12/2003 Reviewer: Level: Date: Atoized Inspecto Date: t6 vf: -{. /Ji fW3,3c

DUKE POWER COMPANY Form NDE-UT-9 ULTRASONIC BEAM ANGLE MEASUREMENT RECORD Revision 3 d 11 tan 0 = (d/2) t

1. Take thickness measurements between.

wedge locations.

2. Place search unit on straight turn of pipe, and peak the signal.
3. Measure distance (d) between exit points.
4. Calculate beam angle with formula as shown using measured wall thickness.
5. Use the measured beam angle to determine coverage and when plotting any indications.

Pipe Size: 6.0 IN. Pipe Schedule: - - - 80 _ _F7N For thin wall pipe use 2nd Vee path tan 0 = (d/2) 2t Nominal 45 deg: d= Nominal 60 deg: d= Nominal 70 deg: d= o

t=

0 2.9

t=

0.838; 0

t=

0 measured angle= 0.00 deg measured angle= 59.98 deg measured angle= 0.00 deg Item No. C05.011.211 Examiner Level Date Examiner III 3/12/2003 Level Date Date Ps-3 of 9}}

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